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Ezato, Koichiro; Suzuki, Satoshi; Dairaku, Masayuki; Akiba, Masato
Fusion Engineering and Design, 81(1-7), p.347 - 354, 2006/02
Times Cited Count：12 Percentile：63.1(Nuclear Science & Technology)no abstracts in English
Ezato, Koichiro; Suzuki, Satoshi; Dairaku, Masayuki; Akiba, Masato
Fusion Engineering and Design, 75-79, p.313 - 318, 2005/11
Times Cited Count：10 Percentile：56.74(Nuclear Science & Technology)no abstracts in English
Ezato, Koichiro; Suzuki, Satoshi; Sato, Kazuyoshi; Akiba, Masato
Journal of Nuclear Materials, 329-333(1), p.820 - 824, 2004/08
Times Cited Count：6 Percentile：40.72(Materials Science, Multidisciplinary)This paper presents thermal fatigue experiments of a cooling tube with a helical triangular fin on its inner cooled surface, namely a 
. The screw thread is directly shaped in a CuCrZr heat sink bar as a cooling channel. Slits with the width of 1.5 mm are machined at the heated side of the heat sink. The thermal fatigue experiments are carried out at 20 and 30 
by using an electron beam irradiation facility in JAERI. Water leakages from fatigue cracks, which locate at the slit of the heat sink, occurred at around 4500th and 1400th cycles at 20 and 30 , respectively. These results show good agreement with lifetime predictions using Manson-Coffin's law based on finite element analyses. Fractographic observations reveal that the fatigue cracks start from the outer heated surface at the slit region of the cooling channel and propagate toward its inner surface.
Masaki, Kei; Taniguchi, Masaki; Miyo, Yasuhiko; Sakurai, Shinji; Sato, Kazuyoshi; Ezato, Koichiro; Tamai, Hiroshi; Sakasai, Akira; Matsukawa, Makoto; Ishida, Shinichi; et al.
Fusion Engineering and Design, 61-62, p.171 - 176, 2002/11
Times Cited Count：19 Percentile：74.77(Nuclear Science & Technology)A flat carbon fiber composite tile mock-up with screw tubes, which have helical fins like a nut, was fabricated aiming at further improvement of the heat removal performance of the cost-effectively manufactured divertor target for JT-60SC (modified JT-60 as a superconducting coil tokamak). The heat removal performance of the mock-up was successfully demonstrated on the JAERI Electron Beam Irradiation Stand. The estimated heat transfer coefficient of the screw tube at the non-boiling region was roughly 3 times higher than that of the smooth tube. This corresponds to 1.5 times that of the swirl tube. A heat cycle test of 10 MW/m2 showed that the mock-up with the screw tubes could withstand for 1400 cycles. These results indicate that the divertor target plate with the flat carbon fiber composite tile and the screw tube can be a promising candidate for the JT-60SC divertor target.
J.Boscary*; Araki, Masanori; ; *; Akiba, Masato
Fusion Technology, 35(3), p.289 - 296, 1999/05
no abstracts in English
J.Boscary*; Araki, Masanori; J.Schlosser*; Akiba, Masato; F.Escorbiac*
Fusion Engineering and Design, 43(2), p.147 - 171, 1998/00
Times Cited Count：43 Percentile：93.87(Nuclear Science & Technology)no abstracts in English
J.Boscary*; Araki, Masanori; Akiba, Masato
JAERI-Research 97-053, 50 Pages, 1997/08
JAERI-Research-97-053.pdf:1.71MB
no abstracts in English
Araki, Masanori; Sato, Kazuyoshi; ; Akiba, Masato
Fusion Technology, 29, p.519 - 528, 1996/07
no abstracts in English
